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Journal Articles

Sm valence determination of Sm-based intermetallics using $$^{149}$$Sm M$"{o}$ssbauer and Sm L$$_{rm III}$$-edge X-ray absorption spectroscopies

Tsutsui, Satoshi; Higashinaka, Ryuji*; Nakamura, Raito*; Fujiwara, Kosuke*; Nakamura, Jin*; Kobayashi, Yoshio*; Ito, Takashi; Yoda, Yoshitaka*; Kato, Kazuo*; Nitta, Kiyofumi*; et al.

Hyperfine Interactions, 242(1), p.32_1 - 32_10, 2021/12

 Times Cited Count:1 Percentile:84.11(Physics, Atomic, Molecular & Chemical)

JAEA Reports

Poro-elastic parameter acquisition test using siliceous mudstone (Wakkanai formation)

Aoki, Tomoyuki*; Tani, Takuya*; Sakai, Kazuo*; Koga, Yoshihisa*; Aoyagi, Kazuhei; Ishii, Eiichi

JAEA-Research 2020-002, 83 Pages, 2020/06

JAEA-Research-2020-002.pdf:8.25MB
JAEA-Research-2020-002-appendix(CD-ROM).zip:6.63MB

The Japan Atomic Energy Agency (JAEA) has conducted with the Horonobe Underground Research Project in Horonobe, Teshio-gun, Hokkaido for the purpose of research and development related to geological disposal technology for high-level radioactive wastes in sedimentary soft rocks. The geology around the Horonobe Underground Research Laboratory (HURL) is composed of the Koetoi diatomaceous mudstone layer and the Wakkanai siliceous layer, both of which contain a large amount of diatom fossils. Since these rocks exhibit relatively high porosity but low permeability, it is important to investigate the poro-elastic characteristics of the rock mass. For this objective, it is necessary to measure parameters based on the poro-elastic theory. However, there are few measurement results of the poro-elastic parameters for the geology around HURL, and the characteristics such as dependence on confining pressure are not clearly understood. One of the reasons is that the rocks show low permeability and the pressure control during testing is difficult. Therefore, a poro-elastic parameter measurement test was conducted on the siliceous mudstone of the Wakkanai formation to accumulate measurement results on the poro-elastic parameters and to examine the dependence of the parameters on confining pressure. As a result, some dependency of the poro-elastic parameters on confining pressure was observed. Among the measured or calculated poro-elastic parameters, the drained bulk modulus increased, while the Skempton's pressure coefficient, and the Biot-Wills coefficient in the elastic region decreased with the increase in confining pressure. The measurement results also inferred that the foliation observed in the rock specimens might impact a degree of dependency of those parameters on confining pressure.

Journal Articles

New precise measurements of muonium hyperfine structure at J-PARC MUSE

Strasser, P.*; Abe, Mitsushi*; Aoki, Masaharu*; Choi, S.*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; et al.

EPJ Web of Conferences, 198, p.00003_1 - 00003_8, 2019/01

 Times Cited Count:13 Percentile:98.93(Quantum Science & Technology)

Journal Articles

New precise measurement of muonium hyperfine structure interval at J-PARC

Ueno, Yasuhiro*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 238(1), p.14_1 - 14_6, 2017/11

 Times Cited Count:3 Percentile:86.37(Physics, Atomic, Molecular & Chemical)

Journal Articles

New muonium HFS measurements at J-PARC/MUSE

Strasser, P.*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 237(1), p.124_1 - 124_9, 2016/12

 Times Cited Count:7 Percentile:90.88(Physics, Atomic, Molecular & Chemical)

JAEA Reports

A Study of the criticality safety design for the metal fuel recycle system, 2

Nakabayashi, Hiroki; Kurisaka, Kenichi; Sato, Koji; Niwa, Hajime; Aoki, Kazuo*

JAEA-Technology 2006-027, 119 Pages, 2006/03

JAEA-Technology-2006-027.pdf:9.02MB

This report describes a study about the criticality safety design for the large-scale electrorefiner, which is designed in the activities of "The Design Study of Metal Fuel Recycle System (2002)", under the collaboration with Central Research Institute of Electric Power Industry, and the continuation of "A Study of the Criticality Safety Design for the Metal Fuel Recycle System", which was published at September 2003. The report includes a detail design and quantitative criticality parameter limits based on "the mass control supported with chemical form control" concept which is proposed in "A Study of the Criticality Safety Design for the Metal Fuel Recycle System". Furthermore procedures to determine these limits are presented in the report. Next we studied contingencies anticipated under the critical control and executed quantitative criticality safety analyses of models based on these abnormal conditions. The analytical result shows adequate safety margins are existed in the criticality safety design even if many of these contingencies could occur. Moreover we propose a concept of material transfer and production control system, we call it as "Operation by wire", which all equipment and handling machines are electrified and the control system provides completely automated process control and operation. The control system eliminates human errors and violations like over batching error or transfer error in the commercial scale metal fuel recycle system with complicated operation procedures.

JAEA Reports

Investigation on future nuclear power reactors and fuel cycle systems

Otaki, Kiyoshi*; Tanaka, Yoji*; Katsurai, Kiyomichi*; Aoki, Kazuo*

JAERI-Review 2005-035, 79 Pages, 2005/09

JAERI-Review-2005-035.pdf:4.57MB

In order to collect technical information for the assessment on future nuclear power reactors and fuel cycle systems in Japan, investigation has been made on the characteristics and performance of future reactor options including reduced moderation water reactors (RMWRs) and their fuel cycle systems since the fiscal year 1998. The subjects of investigation are divided into three categories; breeder reactors and their fuel cycle, alternative to sodium-cooled FBR systems,plutonium recycling, spent fuel reprocessing and waste disposal. This report is a summary of the investigation carried out so far.

JAEA Reports

A Study of the Criticality Safety Design for the Metal Fuel Recycle System

Nakabayashi, Hiroki; Fujioka, Tsunaaki; Sato, Koji; Aoki, Kazuo*

JNC TN9400 2003-082, 67 Pages, 2003/09

JNC-TN9400-2003-082.pdf:3.02MB

This report accounts for a study about the criticality safety design for the large-scale electrorefiner, which is designed in the activities of "The Design Study of Metal Fuel Recycle System(2002)", under the collaboration with Central Research Institute od Electric Power Industry.

JAEA Reports

A Feasibility study of H$$^-$$ beam extraction technique using YAG laser

Meigo, Shinichiro; Hasegawa, Kazuo; Ikeda, Yujiro; Oigawa, Hiroyuki; Aoki, Nobutada*; Nakagawa, S.*

JAERI-Tech 2002-095, 40 Pages, 2002/12

JAERI-Tech-2002-095.pdf:2.67MB

no abstracts in English

Journal Articles

Economic scale of utilization of nuclear

Takehisa, Masaaki*; Tagawa, Seiichi*; Kashiwagi, Masayuki*; Tominaga, Hiroshi*; Ishikawa, Isamu*; Ooka, Norikazu; Kamada, Toshimitsu*; Hosobuchi, Kazunari*; Makuuchi, Keizo; Takeshita, Hidefumi; et al.

Genshiryoku Riyo No Keizai Kibo; NSA/Commentaries, No.9, 139 Pages, 2001/01

no abstracts in English

Journal Articles

Regrowth of the photoquenchable defect relating to the hopping conduction in arsenic-ion-implanted semi-insulating GaAs

Kuriyama, Kazuo*; Kazama, K.*; Kato, Takashi*; Yamamoto, Shunya; Aoki, Yasushi; Naramoto, Hiroshi

Journal of Applied Physics, 80(8), p.4488 - 4490, 1996/10

 Times Cited Count:1 Percentile:8.26(Physics, Applied)

no abstracts in English

JAEA Reports

None

Aoki, Kenji*; Hibiya, Keisuke*; Shiogama, Yukihiro*; Toida, Masaru*; Fukazawa, E.*; Okutsu, Kazuo*;

PNC TJ1100 95-002, 195 Pages, 1995/03

PNC-TJ1100-95-002.pdf:16.41MB

None

JAEA Reports

Investigation on sealing in geological disposal

Aoki, Kenji*; Hibiya, Keisuke*; Shiogama, Yukihiro*; Toida, Masaru*; Yamamoto, T.*; Yoshida, Hiroshi*; Banno, K.*; Kubota, T.*; Shimizu, Y.*; Okutsu, Kazuo*; et al.

PNC TJ1100 94-001, 69 Pages, 1994/02

PNC-TJ1100-94-001.pdf:4.56MB

None

Journal Articles

Delayed Neutron Noise Characteristics of an In-Pile Fission Product Loop

Tamaoki, Tetsuo*; Sakai, Takuhiko*; Endo, Hiroshi*; Haga, Kazuo; Takahashi, Ryoichi*

Nuclear Technology, 99(1), p.58 - 69, 1992/07

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

None

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 3; Over view of development program

Koyama, Tomozo; Kamiya, Masayoshi; Aoki, Kazuo*; Sawada, Kayo*

no journal, , 

Actinides co-extraction system with direct extraction process using supercritical fluid is developed in JAEA. This report indicates over view of development.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 12; The Outline of the other results of development

Kamiya, Masayoshi; Kaji, Naoya; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

It is shown in this presentation that the outline "development of actinides co-extraction system with direct extraction process using supercritical fluid" and future schedule.

Oral presentation

Development of ITER gyrotron system for the actual equipments

Ikeda, Ryosuke; Oda, Yasuhisa; Kajiwara, Ken; Terakado, Masayuki; Aoki, Takashi; Oshima, Katsumi; Tsubota, Naoaki; Hayashibara, Masashi; Hayashi, Kazuo*; Kobayashi, Takayuki; et al.

no journal, , 

no abstracts in English

Oral presentation

Study on the behavior of concrete lining and rock mass during shaft excavation by means of short step method

Sakai, Kazuo*; Koike, Masashi*; Aoki, Tomoyuki*; Yamamoto, Takuya*; Hatsuyama, Yoshihiro*; Yamazaki, Masanao

no journal, , 

In a construction project of the Horonobe URL, vertical shafts are excavated now by the Short Step method. This paper examines the behavior of concrete lining and rock mass around the shaft. To reflect the excavation sequence, a 3-D analysis is performed, modeling rock mass and support members around an advancing face. The analysis shows well specific phenomena of the Short Step method, as in the rock mass displacement and lining stress. It also reveals lining stress distribution are complex. In future, it is important to investigate lining stress through detailed measurements.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fluid, 5; Distribution coefficient of U and Pu in high concentration condition

Kamiya, Masayoshi; Sano, Yuichi; Miura, Sachiko; Koyama, Tomozo; Aoki, Kazuo*; Sawada, Kayo*

no journal, , 

Processing in high concentration condition is the feature of actinides co-extraction system with direct extraction process using supercritical fluid. Distribution coefficient of U and Pu obtained by experiment indicates that conventional empirical formula is applicable in this condition.

Oral presentation

Development of actinides co-extraction system with direct extraction process using supercritical fruid, 14; Direct extraction test of unirradiated MOX fuel

Kaji, Naoya; Kamiya, Masayoshi; Takahatake, Yoko; Oyama, Koichi; Miura, Sachiko; Koyama, Tomozo; Aoki, Kazuo*; Yamada, Seiya*

no journal, , 

A battery of tests using MOX fuel were performed for development of actinides co-extraction system with direct extraction process using supercritical fluid. The condition that was set up based on consideration of the results of the tests under ordinary pressure, and then was made fine adjusted based on the tests with supercritical fruid. As a result, U, Pu and Am were extracted simultaneously. Comparative test confirmed that U, Pu and Am could be also extracted simultaneously with dodecane as a diluent. While the extraction test of unirradiated MOX fuel with simulated FP, U, Pu was extracted with U and Am, and the Pu residue, that was found at the extraction test of irradiated fuel, was not found. As the result of scrubbing and stripping test, it was showed that traditional extraction process design method could be applied to design scrubbing and stripping process with supercritical fluid.

27 (Records 1-20 displayed on this page)